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Journal Articles

Effect of Variable Angular Piping Bends Geometry on Turbulent Flow of Supercritical Water in an SCWR Plant Piping Network: A Three-Dimensional Computational Fluid Dynamics Investigation

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Mohammad Khan, Jehad Haque, Saad Islam, Lubon Putul, Mehedi Hasan
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2025, 11(3): 031401.
Paper No: NERS-24-1060
https://doi.org/10.1115/1.4067628
Published Online: February 14, 2025
View Articletitled, Effect of Variable Angular Piping Bends Geometry on Turbulent Flow of Supercritical Water in an SCWR Plant Piping Network: A Three-Dimensional Computational Fluid Dynamics Investigation
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Topics: Computational fluid dynamics, Flow (Dynamics), Pipe bends, Pipes, Pressure, Supercritical water reactors, Turbulence, Water, Geometry, Fluids
Journal Articles

An Estimation Method for Bias Error of Measurements by Utilizing Process Data, An Incidence Matrix and a Reference Instrument for Data Validation and Reconciliation: Extension to the Energy Balance Relation

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Akinori Tamura, Yuki Hidaka, Haruhiko Ikeda, Norikazu Hamaura
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2025, 11(2): 021101.
Paper No: NERS-24-1037
https://doi.org/10.1115/1.4066344
Published Online: October 22, 2024
View Articletitled, An Estimation Method for Bias Error of Measurements by Utilizing Process Data, An Incidence Matrix and a Reference Instrument for Data Validation and Reconciliation: Extension to the Energy Balance Relation
Open the PDF for An Estimation Method for Bias Error of Measurements by Utilizing Process Data, An Incidence Matrix and a Reference Instrument for Data Validation and Reconciliation: Extension to the Energy Balance Relation in another window
Topics: Energy budget (Physics), Errors, Flow (Dynamics), Instrumentation, Temperature measurement, Measurement uncertainty, Uncertainty, Sensors, Temperature, Nuclear power stations
Journal Articles

Interactions Between Molten Sodium and Standard Pipe Insulation

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Daniel LaBrier, Jordan Harley, Morgan Robbins
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 030901.
Paper No: NERS-22-1191
https://doi.org/10.1115/1.4062798
Published Online: March 8, 2024
View Articletitled, Interactions Between Molten Sodium and Standard Pipe Insulation
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Topics: Insulation, Sodium, Metals, Temperature
Journal Articles

Development of Analysis Tools for Heat Pipes Used in the Core Cooling of Small Modular Reactors: Potassium Property Correlations

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Thomas Beuthe, Hooman Jazebizadeh, Aleksandar Vasić, Alex Pegarkov, Tarik Kaya, Hussam Zahlan
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021401.
Paper No: NERS-22-1026
https://doi.org/10.1115/1.4062752
Published Online: November 1, 2023
View Articletitled, Development of Analysis Tools for Heat Pipes Used in the Core Cooling of Small Modular Reactors: Potassium Property Correlations
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Topics: Potassium, Temperature, Vapors, Heat pipes
Includes: Supplementary data
Journal Articles

Development of Analysis Tools for Heat Pipes Used in Small Modular Reactors: Sodium Property Correlations

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Thomas Beuthe, Aleksandar Vasić, Chukwudi Azih, Pablo D. G. Maqueo
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Review Articles
ASME J of Nuclear Rad Sci. April 2024, 10(2): 020801.
Paper No: NERS-23-1052
https://doi.org/10.1115/1.4063112
Published Online: October 20, 2023
View Articletitled, Development of Analysis Tools for Heat Pipes Used in Small Modular Reactors: Sodium Property Correlations
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Topics: Sodium, Temperature, Vapors, Heat pipes
Includes: Supplementary data
Journal Articles

An Estimation Method for Bias Error of Measurements by Utilizing Process Data, An Incidence Matrix and a Reference Instrument for Data Validation and Reconciliation

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Akinori Tamura, Yuki Hidaka, Haruhiko Ikeda, Norikazu Hamaura
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041802.
Paper No: NERS-23-1050
https://doi.org/10.1115/1.4062865
Published Online: September 15, 2023
View Articletitled, An Estimation Method for Bias Error of Measurements by Utilizing Process Data, An Incidence Matrix and a Reference Instrument for Data Validation and Reconciliation
Open the PDF for An Estimation Method for Bias Error of Measurements by Utilizing Process Data, An Incidence Matrix and a Reference Instrument for Data Validation and Reconciliation in another window
Topics: Errors, Flow (Dynamics), Instrumentation, Measurement uncertainty, Uncertainty, Nuclear power stations, Sensors, Pipes
Journal Articles

Inverse Heat Conduction Problem in Estimating Nuclear Power Plant Piping Performance

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S. A. Cancemi, R. Lo Frano
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2022, 8(3): 034501.
Paper No: NERS-20-1206
https://doi.org/10.1115/1.4053689
Published Online: May 26, 2022
View Articletitled, Inverse Heat Conduction Problem in Estimating Nuclear Power Plant Piping Performance
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Topics: Filters, Pipes, Signals, Stress, Temperature, Monitoring systems, Nuclear power stations
Journal Articles

Thermal Fatigue of Pressurized Water Reactor Coolant System Loop Drain Lines Due to Outflow Activities

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Yue Zou, Brian Derreberry
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031801.
Paper No: NERS-21-1040
https://doi.org/10.1115/1.4053013
Published Online: May 26, 2022
View Articletitled, Thermal Fatigue of Pressurized Water Reactor Coolant System Loop Drain Lines Due to Outflow Activities
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Topics: Chemistry, Coolants, Fatigue, Flow (Dynamics), Outflow, Pipes, Pressurized water reactors, Stress, Temperature, Thermal stratification
Journal Articles

Deposition of ITER Vacuum Vessel Dust Inside the Pressure Suppression System During a Loss of Coolant Accident: Experimental and Numerical Analyses

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Miriam Ibba, Alessio Pesetti, Michele Raucci, Flavio Parozzi, Roberta Lazzeri, Donato Aquaro
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 042301.
Paper No: NERS-21-1025
https://doi.org/10.1115/1.4050768
Published Online: March 16, 2022
View Articletitled, Deposition of ITER Vacuum Vessel Dust Inside the Pressure Suppression System During a Loss of Coolant Accident: Experimental and Numerical Analyses
Open the PDF for Deposition of ITER Vacuum Vessel Dust Inside the Pressure Suppression System During a Loss of Coolant Accident: Experimental and Numerical Analyses in another window
Topics: Dust, Water, Containers, Vessels, Pipes
Journal Articles

Optimization of the European Sodium Fast Reactor Secondary Sodium Loop as Part of the ESFR-SMART Project

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Joel Guidez, Janos Bodi, Konstantin Mikityuk, Enrico Girardi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011323.
Paper No: NERS-21-1043
https://doi.org/10.1115/1.4052589
Published Online: October 29, 2021
View Articletitled, Optimization of the European Sodium Fast Reactor Secondary Sodium Loop as Part of the ESFR-SMART Project
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Topics: Circuits, Safety, Sodium, Pumps, Pipes, Boilers, Industrial research, Optimization
Journal Articles

Guided Waves Measurement Techniques in Pitch–Catch Configuration

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Francesco Cordella, Francesco Bertoncini, Mauro Cappelli
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2021, 7(3): 032004.
Paper No: NERS-20-1107
https://doi.org/10.1115/1.4049345
Published Online: April 16, 2021
View Articletitled, Guided Waves Measurement Techniques in Pitch–Catch Configuration
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Topics: Waves, Pipes, Signals, Cylinders
Journal Articles

Experimental and Numerical Investigation of Solidification of Gallium in an Initially Emptied Horizontal Pipe Flow

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Shawn Somers-Neal, Alex Pegarkov, Edgar Matida, Vinh Tang, Tarik Kaya
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2021, 7(3): 031602.
Paper No: NERS-20-1052
https://doi.org/10.1115/1.4049096
Published Online: March 16, 2021
View Articletitled, Experimental and Numerical Investigation of Solidification of Gallium in an Initially Emptied Horizontal Pipe Flow
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Topics: Gallium, Metals, Pipes, Solidification, Temperature, Computer simulation, Reynolds number, Flow (Dynamics), Wall temperature
Journal Articles

Modeling and Simulation of Subcooled Coolant Loss Through Circumferential Pipe Leakage

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Sandip Ghosh, Samir Kumar Saha
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2021, 7(3): 034503.
Paper No: NERS-20-1012
https://doi.org/10.1115/1.4048477
Published Online: March 16, 2021
View Articletitled, Modeling and Simulation of Subcooled Coolant Loss Through Circumferential Pipe Leakage
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Topics: Flow (Dynamics), Leakage, Pipes, Simulation, Subcooling, Flashing, Coolants, Fracture (Materials), Modeling, Vapors
Journal Articles

Application of Nonlinear Elastic Wave Spectroscopy in the Field of Nuclear Energy

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J. Patera, J. Jansa
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021803.
Paper No: NERS-20-1108
https://doi.org/10.1115/1.4048238
Published Online: November 16, 2020
View Articletitled, Application of Nonlinear Elastic Wave Spectroscopy in the Field of Nuclear Energy
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Topics: Elastic waves, Excitation, Nuclear power, Spectroscopy, Concretes, Microcracks, Pipes, Steel, Concrete beams, Concrete testing
Journal Articles

Retention of Molten Corium in Calandria Vessel of PHWR With Moderator Drain Pipe

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Pradeep Pandey, Parimal P. Kulkarni, Arun Nayak, Sumit V. Prasad
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011702.
Paper No: NERS-19-1131
https://doi.org/10.1115/1.4046257
Published Online: October 1, 2020
View Articletitled, Retention of Molten Corium in Calandria Vessel of PHWR With Moderator Drain Pipe
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Topics: Pipes, Temperature, Vessels, Heavy water reactors
Journal Articles

Analysis Methods for High Energy Line Break Jet Flows in Nuclear Power Plants

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Marwan Charrouf, Storm Kauffman, Jin-Kyoo Yoon, Sang-Gyu Lee, Taejoon Kim
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2020, 6(4): 041112.
Paper No: NERS-19-1168
https://doi.org/10.1115/1.4047441
Published Online: September 4, 2020
View Articletitled, Analysis Methods for High Energy Line Break Jet Flows in Nuclear Power Plants
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Topics: Computational fluid dynamics, Flow (Dynamics), Jets, Nozzles, Nuclear power stations, Pipes, Pressure, Reflection, Resonance, Waves
Journal Articles

Evaluation of Friction-Factor Correlations at Supercritical Water Conditions in Support of the Canadian SCWR

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A. Nava-Dominguez
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031113.
Paper No: NERS-19-1082
https://doi.org/10.1115/1.4046783
Published Online: June 5, 2020
View Articletitled, Evaluation of Friction-Factor Correlations at Supercritical Water Conditions in Support of the Canadian SCWR
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Topics: Flow (Dynamics), Friction, Pressure drop, Wire, Fuels, Water, Supercritical water reactors, Manufacturing, Pipes
Journal Articles

Numerical Simulation of Siphon Breaker Systems for Open-Type Research Reactors

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Damian E. Ramajo, Santiago F. Corzo, Norberto M. Nigro
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021202.
Paper No: NERS-19-1039
https://doi.org/10.1115/1.4045121
Published Online: February 24, 2020
View Articletitled, Numerical Simulation of Siphon Breaker Systems for Open-Type Research Reactors
Open the PDF for Numerical Simulation of Siphon Breaker Systems for Open-Type Research Reactors in another window
Topics: Flow (Dynamics), Fluids, Pipes, Pressure, Simulation, Water, Computational fluid dynamics, Geometry, Drainage, Computer simulation
Journal Articles

Analyses of Gas Stratification Erosion by a Vertical Jet in Presence of an Obstacle Using the GOTHIC Code

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Michele Andreani, Ralf Kapulla, Stephan Kelm, Domenico Paladino, Sidharth Paranjape
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021110.
Paper No: NERS-19-1072
https://doi.org/10.1115/1.4046296
Published Online: February 24, 2020
View Articletitled, Analyses of Gas Stratification Erosion by a Vertical Jet in Presence of an Obstacle Using the GOTHIC Code
Open the PDF for Analyses of Gas Stratification Erosion by a Vertical Jet in Presence of an Obstacle Using the GOTHIC Code in another window
Topics: Elevations (Drawings), Erosion, Flow (Dynamics), Helium, Pipes, Simulation, Steam, Temperature, Turbulence, Vessels
Journal Articles

RELAP5-3D Three-Dimensional Analysis Based on PHÉNIX Dissymmetric Transient Test

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Vincenzo Narcisi, Fabio Giannetti, Andrea Subioli, Alessandro Del Nevo, Gianfranco Caruso
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011301.
Paper No: NERS-19-1001
https://doi.org/10.1115/1.4044847
Published Online: November 29, 2019
View Articletitled, RELAP5-3D Three-Dimensional Analysis Based on PHÉNIX Dissymmetric Transient Test
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Topics: Coolants, Flow (Dynamics), Modeling, Pipes, Pumps, Sodium, Temperature, Transients (Dynamics), Vessels, Three-dimensional models